Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Juutilainen Pauli"'
Autor:
Rochman Dimitri, Algora Alejandro, Àlvarez-Velarde Francisco, Bardelay Aurélie, Bremnes Øystein, Cabellos Oscar, Cano-Ott Daniel, Capponi Luigi, Carmouze Coralie, Caruso Stefano, Cummings Andrew, Dagan Ron, Fallot Muriel, Fiorito Luca, Giot Lydie, Govers Kevin, Häkkinen Silja, Hannstein Volker, Hoefer Axel, Huynh Tan Dat, Ichou Raphaëlle, Ilas Germina, Juutilainen Pauli, Koszuk Lukasz, Kromar Marjan, Lahaye Sébastien, Lam James, Laugier Frédéric, Launay Agnés, Léger Vincent, Lecarpentier David, Leppanen Jaakko, Malouch Fadhel, Martin Julie-Fiona, McGinnes David, Mills Robert William, Minato Futoshi, Nauchi Yasushi, Ortego Pedro, Petkov Plamen, Romojaro Pablo, Sato Shunsuke, Seidl Marcus, Shama Ahmed, Simeonov Teodosi, Sjöland Anders, Solans Virginie, Sommer Fabian, Tittelbach Sven, Tsilanizara Aimé, Vlassopoulos Efstathios, Vallet Vanessa, Vasiliev Alexander, Watanabe Tomoaki, Žerovnik Gašper
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 10, p 9 (2024)
This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. Needs for precise
Externí odkaz:
https://doaj.org/article/2b742f7a478842a89d12e53316e0faa9
Publikováno v:
Keto, P, Juutilainen, P, Schatz, T, Naumer, S & Häkkinen, S 2022, Waste Management of Small Modular Nuclear Reactors in Finland . VTT Research Report, no. VTT-R-00076-22, VTT Technical Research Centre of Finland, Espoo .
Small modular nuclear reactors (SMRs) represent advanced technology in nuclear energy aim-ing to produce low carbon energy at smaller unit size and enhanced passive safety in compar-ison to traditional nuclear power plants (NPPs). The management of s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::0eb117297a3061d5c05f80574d50e198
https://cris.vtt.fi/en/publications/6f803b81-c028-4517-b8a5-76b9cc0fcb31
https://cris.vtt.fi/en/publications/6f803b81-c028-4517-b8a5-76b9cc0fcb31
Autor:
Juutilainen, Pauli, Häkkinen, Silja
Publikováno v:
Juutilainen, P & Häkkinen, S 2019, Impact of fuel type and discharge burnup on source term . in Proceedings : 28th International Conference Nuclear Energy for New Europe, NENE 2019 . Nuclear Society of Slovenia NENE, 28th International Conference Nuclear Energy for New Europe, NENE 2019, Portorož, Slovenia, 9/09/19 .
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory, other relevant properties of SNF) is essential in the safe handling and final disposal of SNF. For example, decay heat power is one of the key limiting fact
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::16416b2ae6d49abc4f280bf4ce8ce01c
https://cris.vtt.fi/en/publications/e05f5abb-875d-48ad-a39b-a52fce9d1b75
https://cris.vtt.fi/en/publications/e05f5abb-875d-48ad-a39b-a52fce9d1b75
Autor:
Juutilainen, Pauli, Häkkinen, Silja
Publikováno v:
Juutilainen, P & Häkkinen, S 2015, Assessment of proliferation risk related to various fuel cycle scenarios in Finland . in Actinide and Fission Product Partitioning and Transmutation . OECD, Nuclear Science Committee, vol. NEA/NSC/R(2015)2, pp. 202-209, Thirteenth Information Exchange Meeting, Seoul, Korea, Republic of, 23/09/15 . < https://www.oecd-nea.org/science/docs/2015/nsc-r2015-2.pdf >
Some advanced fuel cycle scenarios have been previously calculated with the COSI6 code in order todetermine the potential impact of partitioning and transmutation (P&T) technologies on spent nuclear fuelmanagement in Finland. The focus has been on th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::5b65184ee5e436569ee7f53cd3bf32c8
https://cris.vtt.fi/en/publications/ccc12d97-7fc4-4c52-bf5e-58e27dafc96f
https://cris.vtt.fi/en/publications/ccc12d97-7fc4-4c52-bf5e-58e27dafc96f
Autor:
Juutilainen, Pauli
Publikováno v:
Juutilainen, P 2012, ' Transition from thermal to fast reactors in Finland ', Paper presented at 12th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Prague, Czech Republic, 24/09/12-27/09/12 . < http://www.oecd-nea.org/pt/iempt12/documents/posters/2/juutilainen-full.pdf >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::0afa05fca320c655d07d8ccae0ddcb0c
https://cris.vtt.fi/en/publications/8c4ab5da-3a0f-46c4-8d82-99af6dbec953
https://cris.vtt.fi/en/publications/8c4ab5da-3a0f-46c4-8d82-99af6dbec953
Autor:
Juutilainen, Pauli
Publikováno v:
Juutilainen, P 2012, Fast Reactor Calculations with MCNP, PSG/Serpent and ERANOS . in H Suikkanen (ed.), New Type Nuclear Reactors (NETNUC) 2008-2011 Final Report . Lappeenranta University of Technology, Lappeenranta University of Technology: Energy. Research report, no. 23, pp. 92-102 . < http://urn.fi/URN:ISBN:978-952-265-251-5 >
Evaluated reactor physics benchmark exercises were calculated with both stochastic Monte Carlo and deterministic codes over the period of the NETNUC project. The Monte Carlo codes MCNP and PSG (early version of Serpent) were used to calculate the ben
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::b68b68fa9bf868e6fb229cb6ae0ff86f
https://cris.vtt.fi/en/publications/e40f3952-dd33-44df-8054-39ac0abe2dab
https://cris.vtt.fi/en/publications/e40f3952-dd33-44df-8054-39ac0abe2dab
Autor:
Juutilainen, Pauli
Publikováno v:
Juutilainen, P 2011, ' Fast reactor calculation with the ERANOS code system : Master's Thesis ', Master Degree, Aalto University, Espoo .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::fa3fc6a37c756fa66c081c140d45d0cf
https://cris.vtt.fi/en/publications/b8a0bf27-6254-464a-998e-4cd1d1bfabcd
https://cris.vtt.fi/en/publications/b8a0bf27-6254-464a-998e-4cd1d1bfabcd
Autor:
Juutilainen, Pauli
Publikováno v:
Juutilainen, P 2008, Simulating the behaviour of the fast reactor JOYO . in Proceedings of the International Youth Nuclear Congress 2008 ., 163, IYNC, International Youth Nuclear Congress, IYNC 2008, Interlaken, Switzerland, 20/09/08 . < https://publications.vtt.fi/julkaisut/muut/2008/IYNC_2008_163.pdf >
The benchmark concerning the series of experiments performed for Japanese experimental fast reactor JOYO to determine its basic features was calculated with two Monte Carlo neutron transport codes: MCNP4C and PSG. The purpose of the work was to compa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::f596ccaaea845eb4d914ecb54101ab74
https://cris.vtt.fi/en/publications/02c1783b-87d4-4f1e-983f-1558604ecd4e
https://cris.vtt.fi/en/publications/02c1783b-87d4-4f1e-983f-1558604ecd4e